ML18057A936

301 Exam Administrative Items

ML18057A936
Person / Time
Site:	Summer
Issue date:	02/26/2018
From:	NRC/RGN-II
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Download: ML18057A936 (33)

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ES-201 Examination Preparation Checklist Form ES-201 -1 Facility: V. C_. 51.,w..ir i1 Date of Exation: S.1of. *1o17 Developed by: Written: Facility LiEt NRC II Operating Facility NRC

. Chief Target Task Description (Reference) Examiners Date Initials

1. Examination administration date confirmed (Cia; C.2.ab). For NRC-prepared exams, 240 arrangements are made for the facility to submit reference materials (Ci .e; C.3.c; Attachment 3).

-210 2. NRC examiners and facility contact assigned (C.i.d; C.2.f).

3. Facility contact briefed on security and other requirements (C.2.c). As applicable, the facility

-210 contact submits to the NRC any prescreened K/As for elimination from the written examination outline, with a_description_of the facilitys_prescreening_process_(ES-401,_D.1.b).

-210 4. Reference material due for NRC-prepared exams (C.1.e; C.3.c; Attachment 3). t4,i

-210 5. Corporate notification letter sent (C.2.e).

6. NRC-developed written examination outline (ES-401-1/2 or ES-401N-1/2 and ES-401-3 or

-195 ES-401N-3) sent to facility contact (must be on the exam security agreement) (C.1,ef: C.2.h; C.3,d-e).

7. Operating test outline(s) and other checklists due, including Forms ES-201-2, ES-201-3, ES-301-1, 150 ES-301-2, ES-301-5, and ES-D-1. as applicable (C.1.ef: C.3.de).

8. Operating test outline(s) reviewed by the NRC and feedback provided to facility licensee (C.2.h:

136 C.3.de).

9. Proposed examinations (written, JPM5, and scenarios, as applicable) and outlines (Forms ES-301-1, ES-301-2, ES-D-1. ES-401-1/2 or ES-401N-1/2, and ES-401-3 or ES-401N-3);

-75 supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5. ES-301-6, ES-401-6, ES-401N-6, and any Form ES-201-2 and ES-201-3 updates): and reference materials due (C.1.eh: C.3.d).

10. Examinations prepared by the NRC are approved by the NRC supervisor and forwarded for facility licensee review (C.1.i; C.2.h: C.3.fg). v1fl

-60 11. Preliminary waiver/excusal requests due (C. I rn: C.2.c; ES-202).

-50 12. Written exam and operating test reviews completed (C.3.f).

13. Examination review results discussed between the NRC and facility licensee (C.1 .i; C. 1 kI:

C.2.h: C3.g). The NRC and the facility licensee conduct exam preparatory week.

14. Preliminary license applications and waiver/excusal requests, as applicable (NRC Form 398) due 30 (C.i.m; C2.i: ES-202).

15. Final license applications and waiver/excusal requests, as applicable (NRC Form 398), due and 14 Form ES-201-4 prepared (C.1.m: C.2.k: ES-202).

-7 16. Written examinations and operating tests approved by the NRC supervisor (C.2.jk; C.3.h).

-7 17. Request facility licensee management feedback on the examination (C.2.l).

18. Final applications reviewed; one or two tif more than 10) applications audited to confirm

-7 qualifications/eligibility: and examination approval and waiver/excusal letters sent (C.2.k; Attachment 5: ES-202. C.3.j: ES-204).

-7 19. Proctoring/wrthen exam administration guidelines reviewed th facility licensee (C.3.k).

-7 20. Approved scenarios and job performance measures distributed to NRC examiners (C.3.i).

Target dates are based on facility-prepared examinations and the examination date identified in the corporate notification letter.

These dates are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

ES-201, Page 29 of 32

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: VC. U, j t1&y Date of Examination:

Initials Item Task Description

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401 N.

A b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 or ES-401N and whether all K/A categories are appropriately sampled. 4 T . .

E c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

N

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. -

2. a. Using Form ES-301 -5, verify that the proposed scenario sets cover the required number of /Jj jI normal evolutions, instrument and component failures, technical specifications, and major P S transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected number and A)/A.

U mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301 -4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301 -2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed W among the safety functions as specified on the form A (2) task repetition from the last two NRC examinations is within the limits specified on the form L (3) no tasks are duplicated from the applicants audit test(s)

K (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on I the form.

H A b. Verify that the administrative outline meets the criteria specified on Form ES-301 -1:

(1) the tasks are distributed among the topics as specified on the form U (2) at least one task is new or significantly modified G (3) no more than one task is repeated from the last two NRC licensing examinations -

H

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. -

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. -

R d. Check for duplication and overlap among exam sections. 7 p J4 L e. Checktheentireexamforbalanceofcoverage.7 4j.

f. Assess whether the exam fits the appropriate job level (RD or SRO). T Date

a. Author 7

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Supervisor 7) ic) i (.

Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

w Not applicable for NRC-prepared examination outlines.

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: c.... ( Date of Examination: q_(

Initials Item Task Description a b* c#

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401 N. N/A

b. Assess whether the outline was systematically and randomly prepared in accordance with s1-z c.

T Section D.1 of ES-401 or ES-401 N and whether all K/A categories are appropriately sampled.

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

N

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major J 4q S transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number and u mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed W among the safety functions as specified on the form A (2) task repetition from the last two NRC examinations is within the limits specified on the form L (3) no tasks are duplicated from the applicants audit test(s)

K (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on T the form.

H R b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form U (2) at least one task is new or significantly modified G (3) no more than one task is repeated from the last two NRC licensing examinations H

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. C

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

C IA E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. .

R d. Check for duplication and overlap among exam sections. Wi .

L e. Check the entire exam for balance of coverage. [ jw3 f.__Assess_whether the_exam_fits_the_appropriate_job_level_(RO_or_SRO).

Printed Nam u Date

a. Author or4JSI7P#I Zjir/ 1(0

b. Facility Reviewer (*) E4V

c. NRCChiefExaminer(#) I6QK . iz/ttj,i,

d. NRC Supervisor 91I (i j Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines.

k EbS - 4V44L4tS 4 lLMdf.

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: t/ C. $Lijø.ej CU 1 I)Date offfxamination: I) tO)J Operating Test Number: Z.I1 )o)

1. General Criteria Initials a b c1

a. The operating test conforms to the previously approved outline; changes ate consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).

There is no day-to-day repetition between this and other operating tests to be administered b.

during this e)caminatiOn.

c. The operating test shall not duplicate items from the applicants audit test(s) (see Section D.1.a.). j within

d. Overlap with the written examInation and between different parts of the operating test is acceptable limits.

petent

e. It appears that the operating test will differentiate between competent and less-than-com applicants at the desIgnated license level.

2. Walkthrough Criteria

a. Each JPM includes the following, as applicable:

• initial conditions initiating cues

• references and tools, including associated procedures

• reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be lime critical by the facility licensee

• operationally important specific performance criteria that include detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applIcant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administrative walkthrough outlines (Forms ES-301-1 and ES-301-2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distributIon, bank use, repetition from the last two NRC examinations) specified on those forms and Form ES-201-2.

3. Simulator CrIteria with The associated simulator operating tests (scenario sets) have been reviewed in accordance Form ES-301-4, and a copy Is attached.

Printed Na igna e Date

a. Author

b. Facility Reviewer() V .,f// t /7

c. NRC Chief Examinerf#) M.

d. NRC Supervisor 7

The facility licensee signature is not applicable for NRC-developed tests.

is required.

1. The independent NRC reviewer initials items in column c; the chief examiner concurrence ES-301, Page 24 of 33

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: ] -,

Date of Exam:

fJ,Q 117 Scenario Numbers: I / 2 / Operating Test No,173°l Initials QUALITATIVE ATTRIBUTES a b* #

1. The initial conditions are realistic in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.

2. The scenarios consist mostly of related events. I

3. Each event description consists of ihe following:

. the point In the scenario when it is to be initiated

• the malfunction(s) or conditions that are entered to initiate the event

• the symptoms/cues that will be visible to the crew

• the expected operator actions (by shift position)

. the event termination point (if applicable)

4. The events are valid with regard to physics and thermodynamics.

5. Sequencing and timing of events is reasonable and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.

6. If time compression techniques are used, the scenario summary cleariy so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints.

Cues are given.

7. The simulator modeling is not altered. :3_

8. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

9. Scenarios are new or significantly modified in accordance with Section D.5 of ES-301.  %

10. All individual operatorcompetencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

11. The scenario set provides the opportunity for each applicant to be evaluated in each of the applicable rating factors. (Competency rating factors as described on Forms ES-303-1 and ES-303-3.)

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

13. Applicants are evalualed on a similar number of preidentltied critical tasks across scenarios, when possible.

14. The level of difficulty is appropriate to support licensing decisions for each crew cositlon.

Target Quantitative Attributes per Scenario (See Section D.5.d) Actual Attributes -- --

1. / # __

1. Maitunctions after EOP entry (12) / / *5;_

2. Abnormal events (24) 4 / 4 / 4 I 4 LI I / I / I I I

3. Major transients (12) 2 / 2 / 1 I 3

4. EOPs entered/requiring substantive actions (12)

/ / 1 / 1

5. Entry into a contingency EOP with substantive actions (1 per scenario 1 0 set) -

6. Preidentlfied critical tasks ( 2) 2 / 4 / 4 I 5 The facility licensee signature is not applicable for NRC-developed tests.

1. An independent NRC reviewer initials items in column c; chief examiner concurrence is required.

ES-301, Page 25 of 33

ES4OI, Rev. 10 PWR Examination Outline Form ES4OI-2 Facility: VCSummer DateofExam: 2017 -

RO K/A Category Points SRO-Only Points Tier Group KK A2 G* Total KKKKAAAAIG 1 2 3 4 5 6 1 2 3 41* Total i 1 3 3f 3 3 18 3 3 6 2 1 2 1 9 2 2 4 N/A N/A Evolutions Tier Totals 4 5 5 4 5 4 27 5 5 10 T1 I =1 1 2312132233 2j3 3 28 3 2 5

2. 01 1 3

1 10 2 1 Plant 2

1 ..iI.T_1 1 1 1 1__[i 41 Systems TierTotals 3 ff 38 3 8

3. Generic Knowledge and Abilities 1 21 3 J4 10 1 2 [ 3 4 7 Categories 2 2__f 3 3 - 2 1 [ 2 2

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO only outlines (I.e., except for one category in TIer 3 of the SRO-only, the her Totals In each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

2. The point total for each group and tier in the proposed outline must match that specified In the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.

7* *fl generic (G) K/As In Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.1 .b of ES-401 for the applicable KA5.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form E5-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..

ES-401, REV 10 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KP NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 008AK2.02 Pressurizer Vapor Space Accident! 3 2.7 2.7 Sensors and detectors 009EK2.03 Small Break LOCA /3 3 3.3 S/Gs Oil EG2.2,36 Large Break LOCA I 3 3.1 4.2 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations O15AAJ.O6 RCPMalfunctionsl4 3.1 2.9 j CCWS 022AK1 .04 Loss of Rx Coolant Makeup / 2 2.9 3 Reason for changing from manual to automatic control of charging flow valve controller 025AA2.06 Loss of RHR System /4 3.2 3.4 Existence of proper RHR overpressure protection 027AA1 .01 Pressurizer Pressure Control System 4 3.9 1 U U PZR heaters, sprays, and PORVs Malfunction I 3 029EA1 .08 Ar/VS I 1 4.5 4.5 U U U U U U U Reactor trip switch pushbutton O38EK1 .01 Steam Gen. Tube Rupture / 3 3.1 3.4 Use of steam tables 054AA2.03 Loss of Main Feedwater /4 4.1 4.2 U U U U U U U U U U Conditions and reasons for AFW pump startup 055EG2.4.6 Station Blackout / 6 3.7 4.7 U U U U U U U U U U Knowledge symptom based EOP mitigation strategies.

Page 1 of2 7/13/2016 11:14AM

ES-401, REV 10 TI GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 057AK3.01 Loss of Vital AC Inst. Bus /6 41 4.4 Actions contained in EOP for loss of vital ac electrical instrument bus 058AA2.01 Loss of DC Power! 6 3.7 4.1 That a loss ofdc power has occurred; verification that substitute power sources have come on line 062AG2.4.46 Loss of Nuclear Svc Water / 4 4.2 4.2 j Ability to verify that the alarms are consistent with the plant conditions.

077AK1 .01 Generator Voltage and Electric Grid 3.3 3.5 U U U U U Definition of the terms: volts, walls, amps, VARS, power Disturbances / 6 factor WEO4EK2.2 LOCA Outside Containment / 3 3.8 4.0 Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 1 EK3.4 Loss of Emergency Coolant Recirc. /4 3.6 3.8 RD or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

WE12EK3.2 Steam Line Rupture - Excessive Heat 3.3 3.9 Normal, abnormal and emergency operating procedures Transfer /4 associated with (Uncontrolled Depressurization of all Steam Generators).

Page 2 of2 7/13/2016 11:14AM

ES-401, REV 10 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001AA2.05 Continuous Rod Withdrawal I 1 4.4 4.6 Uncontrolled rod withdrawal from available indications 028AK3.03 Pressurizer Level Malfunction / 2 3.5 4.1 False indication of PZR level when PORV or spray valve is open and RCS saturated O6OAK1.01 Accidental Gaseous Radwaste Rel. /9 2.5 3.1 Types of radiation, their units of intensity and the location of sources of radiation in a nuclear reactor power plant 067AA2.15 Plant Fire On-site / 8 2.9 3.9 Requirements for establishing a fire watch 068AG2.2.22 Control Room Evac. / 8 4.0 4.7 J Knowledge of limiting conditions for operations and safety limits.

076AA1 .04 High Reactor Coolant Activity / 9 3.2 3.4 Failed fuel-monitoring equipment WEO8EK2.1 RCS Overcooling - PTS / 4 3.4 3.7 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE1 0EK2.2 Natural Circ. With Seam Voidl 4 3.6 3.9 Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WE1 5EK3.l Containment Flooding /5 2.7 2.9 Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.

Page 1 of 1 7/13/2016 11:15AM

ES-401, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K6.14 Reactor Coolant Pump 2.6 2.9 Starting requirements 004K1.30 Chemical and Volume Control 2.9 3.1 j Relationship between letdown flow and RCS pressure 005A4.02 Residual Heat Removal 3.4 3.1 Heat exchanger bypass flow control 005K4.12 Residual Heat Removal 3.1 3.7 Lineup for piggyback mode with CSS 006K2.02 Emergency Core Cooling 2.5 2.9 Valve operators for accumulators 006K5.04 Emergency Core Cooling 2.9 3.1 Brittle fracture, including causes and preventative actions 007K4.Ol Pressurizer Relief/Quench Tank 2.6 2.9 Quench tank cooling 008K3.03 Component Cooling Water 4.1 4.2 H H RCP 010A4.02 Pressurizer Pressure Control 3.6 3.4 H H H H H H H H H H PZR heaters H H H Incorrect channel bypassing 012A2.03 Reactor Protection 3.4 3.7 H H H H H H H 013K2.Ol Engineered Safety Features Actuation 3.6 3.8 H H H H H H H H H H ESFAS/safeguards equipment control Page 1 of 3 7/13/2016 11:19AM

ES-401, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO 022A3.Ol Containment Cooling 4.1 4.3 Initia tion of safeguards mode of operation 022A4.Ol - Containment Cooling 3.6 3.6 CCS fans 026G2.2.38 Containment Spray 3.6 4.5 Knowledge of conditions and limitations in the facility licens 039K4.02 Main and Reheat Steam 3.1 3.2 Utilization of T-ave. program control when steam dumping through atmospheric reliefldump valves, including I-ave.

limits Feed Pump speed, including normal control speed for ICS 059A1.07 Main Feedwater 2.5 2.6 E 059K3.03 Main Feedwater 3.5 3.7. S/GS 061K5.O1 Auxiliary/Emergency Feedwater 3.6 3.9 Relationship between AFWS0w and RCS heat transfer 0611<6.01 Auxiliary/Emergency Feedwater 2.5 2.8 Controllers and positioners 062K1.04 AC Electrical Distribution 3.7 4.2 Off-site power sources 063A1 .01 DC Electrical Distribution 2.5 3.3 Battery capacity as it is affected by discharge rate 064A1 .05 Emergency Diesel Generator 2.5 2.5 ED/G room temperature Page2of3 7/13/2016 11:19AM

ES4OI, REV 10 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO 064A2.07 Emergency Diesel Generator 2.5 2.7 Consequences of operating under/over-excited 073A2.02 Process Radiation Monitoring 2.7 3.2 Detector failure 076G2.4.46 Service Water 4.2 4.2 LI Ability to verify that the alarms are consistent with the plant conditions.

076K2.Ol Service Water 2.7 2.7 Service water 078G2.2.38 Instrument Air 3.6 4.5 DEED EEEEE Knowledge of conditions and limitations in the facility licens 103A3.Ol Containment 3.9 4.2 Containment isolation Page 3 of 3 7/13/2016 11:19AM

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ES-401, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-40f-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l .3 Conduct of operations 3.7 3.9 j Knowledge of shift or short term relief turnover practices.

G2.l .37 Conduct of operations 4.3 4.6 Knowledge of procedures, guidelines or limitations associated with reactivity management G* Equipment Control S uli-wni1 lin3

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. 1.. 31 .3 J I)

_4o G2.2.36 Equipment Control 3.1 4.2 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations G2.3.l3 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.l4 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 j Knowledge of radiation exposure limits under normal and emergency conditions G2.4.2 Emergency Procedures/Plans 4.5 4.6 U U Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

G2.4.21 Emergency Procedures/Plans 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions G2.4.43 Emergency Procedures/Plans 3.2 3.8 U U U U U U U U U U Knowledge of emergency communications systems and techniques.

Page 1 of 1 7/13/2016 11:18AM

ES-401, REV JO SRO TI GI PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO LI LI LI If reactor should have tripped but has not done so, manual[

007EA2.04 Reactor Trip - Stabilization - Recovery! 4.6 4.4 LI LI LI LI LI LI trip the reactor and carry out actions in AT\NS EOP 1

009EA2.06 Small Break LOCA I 3 3.8 4.3 Whether PZR water inventory loss is imminent 027AA2.12 Pressurizer Pressure Control System 3.7 3.8 LI PZR level Malfunction! 3 040AG2.2.38 Steam Line Rupture - Excessive Heat 3.6 4.5 Knowledge of conditions and limitations in the facility licens Transfer! 4 057AG2.l .30 Loss of Vital AC Inst. Bus! 6 4.4 40 LI Ability to locate and operate components, including local controls.

Knowledge of local auxiliary operator tasks during 062AG2.4.35 Loss of Nuclear Svc Water! 4 3.8 4.0 LIED LI LI LI LI LI LI LI emergency and the resultant operational effects Page 1 of 1 711312016 11:18AM

ES-401, REV 10 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES4O1-2 KA NAME I SAFETY FUNCTION: IR Kl K2 k3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 059AG2.4.21 Accidental Liquid RadWaste Rel. / 9 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions 067AA2.14 Plant Fire On-site /8 3.2 4.3 Equipment that will be affected by fire suppression activities in each zone weO6EG2.4.1 1 Degraded Core Cooling /4 4.0 4.2 Knowledge of abnormal condition procedures.

WE5EA2.1 Containment Flooding / 5 2.7 3.2 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Page 1 of I 7/13/2016 11:17AM

ES-401, REV 10 SRO T201 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 004G2.l .23 Chemical and Volume Control 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

006G2.2.44 Emergency Core Cooling 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system 01 3A2.04 Engineered Safety Features Actuation 3.6 4.2 Loss of instrument bus 059A2.03 Main Feedwater 2.7 3.1 E j Overfeeding event 064A2.08 Emergency Diesel Generator 2.7 3.1 Consequences of opening/closing breaker between buses (VARS, out-of-phase, voltage)

Page 1 oil 7/13/2016 11:17AM

ES-401, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002A2.Q4 Reactor Coolant 4.3 4.6 Loss of heat sinks 01 1G2.4.46 Pressurizer Level Control 4.2 4.2 LI LI LI LI LI LI LI Ability to verify that the alarms are consistent with the plant conditions.

041A2.02 Steam Dump/Turbine Bypass Control 3.6 3.9 LI LI LI LI LI LI LI (j LI LI LI Steam valve stuck open Page 1 of 1 7/13/2016 11:17AM

ES-401, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES4OI-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .34 Conduct of operations 2.7 3.5 Knowledge of primary and secondary chemistry limits G2. 1.6 Conduct of operations 3.8 4.8 Ability to manage the control room crew during plant transients.

G2.2.6 Equipment Control 3.0 3.6 Knowledge of the process for making changes to procedure G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties Radiation Control 3.8

opootor duboo4 2 3 Ce pwo ie5e/.Y Ahy+

G2.4. 19 Emergency Procedures/Plans 3.4 4.1 Knowledge of EOP layout, symbols and icons.

G2.4.44 Emergency Procedures/Plans 2.4 4.4 Knowledge of emergency plan protective action recommendations.

Page 1 of 1 7/13/2016 11:16AM

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility:V.C. &ii1- i)ate of Exam: 9jt/I7 Exam Level: RO /SRO 7

[

tern Description Initials a b c 1 Clean answer sheets copied before grading

2. Proposed answer key changes and question deletions justified and documented (facility reviewer initials not required ,

(N/R) if NO post-examination comments are submitted)

3. Applicants scores checked for addition errors (reviewers spot check > 25% of examinations)

4. Grading for all borderline cases (80% +/-2% overall and 70% or 80%, as applicable, +/-4% on the SRO-only exam) reviewed in -

detail 1

5. All other failing examinations checked to ensure that grades are justified %L

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of 1j questions missed by one-half or more of the applicants Date Printed Name/Signature

a. Grader c10 71liJ 7L_-_P 7

b. Facility Reviewer(*)

c. NRC Chief Exarniner(*)

d. NRC Supeisor(*) o1I

(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are requited.

ES-403, Page 6 of 6

Neil E. Constance Manager, Nuclear Training 803.345.4028 December 15, 2016 A SCANA COMPANY Mr. Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety U. S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257

Subject:

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATION OUTLINES Based on the guidelines in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10, in particular ES-201, "Initial Operator Licensing Examination Process" and ES-301, "Preparing Initial Operating Tests," South Carolina Electric & Gas Company (SCE&G) has enclosed the following information for your consideration:

• Enclosure 1 ES-201-2, Examination Outline Quality Checklist

• Enclosure 2 ES-201-3, Examination Security Agreement

• Enclosure 3 ES-301-1, Administrative Topics Outline

• Enclosure 4 ES-301-2, Control Room/In-Plant Systems Outline

• Enclosure 5 ES-301-5, Transient and Event Checklist

• Enclosure 6 ES-D-1s, Scenario Outlines The enclosed examination materials have been independently reviewed by Mr. Danny L. Rhymer, Shift Manager, Operations.

In accordance with NUREG-1021, this material must be withheld from public disclosure until the examinations are complete.

Should there be any questions, please contact Mr. Robert N. Johnston, Nuclear Trainer Principle at (803) 931-5173.

Very truly yours,

?Ja---.t-v Neil E. Constan" I t/15'/;{i TS/NEC/tb Enclosures c: (Without Enclosure unless noted)

M. A. Bates (NRC e-mail notification) RTS (CR-16-06263)

NRC Resident Inspector File (814.04, RR 1050)

PRSF (RC-16-0172)

V. C. Summer Nuclear Station

• P. 0. Box 88

• Jenkinsville, SC* 29065, F (803) 941-9776

Neil E. Constance Manager, Nuclear Training 803.345.4028 July 12, 2017 A SCANA COMPANY Mr. Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety U. S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257

Subject:

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 REACTOR AND SENIOR REACTOR OPERATOR WRITTEN EXAMINATION, OPERATING TEST, AND SUPPORTING REFERENCE MATERIAL Based on the guidelines in NUREG-1021, "Operator Licensing Examination Standards for Power Reactors", Revision 11, in particular ES-301, "Preparing Initial Operating Tests," South Carolina Electric & Gas Company is providing the following information for your consideration.

• ES-201-2, Examination Outline Quality Checklist

• ES-201-3, Examination Security Agreement

• ES-301-1, Administrative Topics Outline

• ES-301-2, Control Room/In-Plant Systems Outline

• ES-301-3, Operating Test Quality Checklist

• ES-301-4, Simulator Scenario Quality Checklist

• ES-301-5, Transient and Event Checklist

• ES-301-6, Competencies Checklist

• ES-401-4, Record of Rejected K/As

• ES-401-6, Written Exam Quality Checklist

• Written Exam Hard Copy with Supporting Documentation

• Written Exam Electronic Files on DVD-ROM

• Operational Exam Hard Copy

• Operational Exam Electronic Files on DVD-ROM

• Supporting Reference Documentation Files on DVD-ROM The enclosed examination materials have been independently reviewed by Mr. Danny Rhymer, Shift Manager. In accordance with NUREG-1021, this material must be withheld from public disclosure until the examinations are complete.

Should there be any questions, please contact Mr. Robert N. Johnston at (803) 931-5173.

Very truly yours, Neil E. Constance TS/NEC/sr Enclosures c: (Without Enclosures unless noted) NRG Resident Inspector G. J. McCoy RTS (CR-16-06263)

D. M. Bacon File (814.04, RR 1050)

R. N. Johnston OMS (RC-17-0095)

V. C. Summer Nuclear Station, P. 0. Box 88, Jenkinsville, South Carolina, 29065, F (803) 941-9776, www.sceg.com

Neil E. Constance Manager, Nuclear Training 803.345.4028 October 4, 2017 A SCANA COMPANY Mr. Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety U.S. Nuclear Regulatory Commission, Region II 245 Peachtree Center Ave. N.E., Suite 1200 Atlanta, GA 30303-1257

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 INITIAL OPERATOR LICENSE EXAMINATION POST EXAMINATION SUBMITTAL The VCSNS Initial Operator License Examination was administered during the weeks of September 18, 2017 and September 25, 2017. The VCSNS Initial License Written Examination was administered on September 28, 2017. VCSNS is enclosing the following as required by Revision 11 of NUREG 1021, "Operator Licensing Examination Standards for Power Reactors:"

1. Each applicant's original answer and examination cover sheets plus two clean copies of each applicant's answer sheet;

2. The master examinations and answer keys;

3. Written examination seating chart; and

4. Written examination performance analysis.

There were no questions asked by applicants during the written examination. Additionally, there are no formal post-examination comments for any portion of the examination. VCSNS does not request a change to any examination item. As agreed, the examination security agreement will be sent via email at a later date.

If you require any additional information or have any questions, please contact Robert Johnston at (803) 931-5173.

Very truly yours, Mf_

Neil E. Constance TS/NEC/hk Enclosures c: (Without Enclosure unless noted)

C. Haney RTS (CR-16-06263)

D. M. Bacon (NRC e-mail notification) File (814.04, RR 1050)

NRC Resident Inspector PRSF (RC-17-0142)

V. C. Summer Nuclear Station* P. 0. Box 88* Jenkinsville, South Carolina* 29065* F (803) 941-9776* www.sceg.com